Aerosol Modeling of Hypothetical LMFBR Accidents.

Koontz, R.L.; Baurmash, L.; Nelson, C.T.; Hausknecht, D.F.; Vaughan, E.U.; Silberberg, Martin; Morewitz, H.A.

doi:10.2172/4083242

Cited by 4 publications

(2 citation statements)

References 7 publications

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“…Perhaps the most widely available of the reactor accidents codes is HAA-3 (Heterogenous Aerosol Agglomeration, Version 3) developed by several workers (Greenfield et al 1969(Greenfield et al , 1970Koontz et al 1970) and documented by Hubner, Vaughan, and Baurmash (1973). HAA-3 accounts for Brownian and gravitational agglomeration of particles, diffusion to the walls, and gravity settling.…”

Section: Fixed Distribution Typementioning

confidence: 99%

Review of models applicable to accident aerosols

Glissmeyer¹

1983

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Estimations of potential airborne particle releases are essential in safety assessments of nuclear fuel facilities. This report is a review of aerosol behavior models that have potential applications for predicting aerosol characteristics in compartments containing accident-generated aerosol sources. Such characterization of the accident-generated aerosols is a necessary step toward estimating their eventual release in any accident scenario. Existing aerosol models can predict the size distribution, concentration, and composition of aerosols as they are acted on by ventilation, diffusion, gravity, coagulation and other phenomena. Models developed in the fields of fluid mechanics, indoor air pollution and nuclear reactor accidents are reviewed with this nuclear fuel facility application in mind. The various capabilities of modeling aerosol behavior are tabulated and discussed, and recommendations are made for applying the models to problems of differing complexity.

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Section: Fixed Distribution Typementioning

confidence: 99%

Review of models applicable to accident aerosols

Glissmeyer¹

1983

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“…The parameter values were selected based on the results of experimental data generated by AI. The sensitivity of these parameters on the rate of fallout have been investigated and reported in Reference (21). A Stoke's correction factor change from 1.0 to 0.33 increases the long term mass leakage by a factor of 3.0.…”

Section: Leak Rates From Containment Structuresmentioning

confidence: 99%